Computational Methods for Multidimensional Neutron Diffusion Problems

A neutronic module for the solution of two-dimensional steady-state multigroup diffusion problems in nuclear reactor cores is developed. The module can produce both direct fluxes as well as adjoints, that is, neutron importances. Different numerical schemes are employed. A standard finite-difference...

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Main Authors: Song Han, Sandra Dulla, Piero Ravetto
Format: Article
Language:English
Published: Wiley 2009-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2009/973605
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author Song Han
Sandra Dulla
Piero Ravetto
author_facet Song Han
Sandra Dulla
Piero Ravetto
author_sort Song Han
collection DOAJ
description A neutronic module for the solution of two-dimensional steady-state multigroup diffusion problems in nuclear reactor cores is developed. The module can produce both direct fluxes as well as adjoints, that is, neutron importances. Different numerical schemes are employed. A standard finite-difference approach is firstly implemented, mainly to serve as a reference for less computationally challenging schemes, such as nodal methods and boundary element methods, which are considered in the second part of the work. The validation of the methods proposed is carried out by comparisons of results for reference structures. In particular a critical problem for a homogeneous reactor for which an analytical solution exists is considered as a benchmark. The computational module is then applied to a fast spectrum system, having physical characteristics similar to the proposed lead-cooled ELSY project. The results show the effectiveness of the numerical techniques presented. The flexibility and the possibility to obtain neutron importances allow the use of the module for parametric studies, design assessments, and integral parameter evaluations as well as for future sensitivity and perturbation analyses and as a shape solver for time-dependent procedures.
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spelling doaj-art-839e539d260c48b283e5bfbf4b9479b82025-02-03T06:13:00ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832009-01-01200910.1155/2009/973605973605Computational Methods for Multidimensional Neutron Diffusion ProblemsSong Han0Sandra Dulla1Piero Ravetto2Department of Nuclear and Reactor Physics, AlbaNova University Centre, Royal Institute of Technology 106 91 Stockholm, SwedenDipartimento di Energetica, Politecnico di Torino, Corso Duca degli Abruzzi 24, 10129 Torino, ItalyDipartimento di Energetica, Politecnico di Torino, Corso Duca degli Abruzzi 24, 10129 Torino, ItalyA neutronic module for the solution of two-dimensional steady-state multigroup diffusion problems in nuclear reactor cores is developed. The module can produce both direct fluxes as well as adjoints, that is, neutron importances. Different numerical schemes are employed. A standard finite-difference approach is firstly implemented, mainly to serve as a reference for less computationally challenging schemes, such as nodal methods and boundary element methods, which are considered in the second part of the work. The validation of the methods proposed is carried out by comparisons of results for reference structures. In particular a critical problem for a homogeneous reactor for which an analytical solution exists is considered as a benchmark. The computational module is then applied to a fast spectrum system, having physical characteristics similar to the proposed lead-cooled ELSY project. The results show the effectiveness of the numerical techniques presented. The flexibility and the possibility to obtain neutron importances allow the use of the module for parametric studies, design assessments, and integral parameter evaluations as well as for future sensitivity and perturbation analyses and as a shape solver for time-dependent procedures.http://dx.doi.org/10.1155/2009/973605
spellingShingle Song Han
Sandra Dulla
Piero Ravetto
Computational Methods for Multidimensional Neutron Diffusion Problems
Science and Technology of Nuclear Installations
title Computational Methods for Multidimensional Neutron Diffusion Problems
title_full Computational Methods for Multidimensional Neutron Diffusion Problems
title_fullStr Computational Methods for Multidimensional Neutron Diffusion Problems
title_full_unstemmed Computational Methods for Multidimensional Neutron Diffusion Problems
title_short Computational Methods for Multidimensional Neutron Diffusion Problems
title_sort computational methods for multidimensional neutron diffusion problems
url http://dx.doi.org/10.1155/2009/973605
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AT sandradulla computationalmethodsformultidimensionalneutrondiffusionproblems
AT pieroravetto computationalmethodsformultidimensionalneutrondiffusionproblems